ANALYSIS OF FAST NEUTRON TRANSPORT IN CHLORIDE SALTS USING MONTE CARLO METHOD

Authors

  • Ondřej Šťastný Brno University of Technology, State Office for Nuclear Safety Department of Non - Proliferation, Czech Republic
  • Karel Katovský Brno University of Technology, Czech Republic
  • Dušan Král Brno University of Technology, Czech Republic
  • Antonín Krása Belgian Nuclear Research Centre, Belgium
  • Kamil Števanka Brno University of Technology, Czech Republic

DOI:

https://doi.org/10.14311/APP.2020.28.0042

Keywords:

Accelerator driven systems, fast neutrons, ADAR, chloride salts, MCNP, molten salt reactors, Monte Carlo simulations

Abstract

The aim of this paper is to present results of fast neutron behavior analysis within the chloride salts environment using simulations based on Monte Carlo method (MCNP 6.2). Three non-fueled salts (NaCl, KCl, MgCl2) and two salts containing fissile material (UCl3, ThCl4) were studied. Results of this theoretical study will be used for design of an experimental assembly, which will serve to achieve goals of the international research project ADAR (Accelerator Driven Advanced Reactor). One of the project objectives is to investigate chloride salts as potential coolant and a dissolved fuel carrier of advanced nuclear reactor cooled by molten salts and driven by an accelerator.

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Author Biographies

Ondřej Šťastný, Brno University of Technology, State Office for Nuclear Safety Department of Non - Proliferation, Czech Republic

Brno University of Technology, Faculty of Electrical Engineering and Communication, Department of Electrical Power Engineering, Technická 10, 616 00 Brno, Czech Republic

State Office for Nuclear Safety Department of Non - Proliferation, Senovážné námestí 9, 110 00 Prague, Czech Republic

Karel Katovský, Brno University of Technology, Czech Republic

Brno University of Technology, Faculty of Electrical Engineering and Communication, Department of Electrical Power Engineering, Technická 10, 616 00 Brno, Czech Republic

Dušan Král, Brno University of Technology, Czech Republic

Brno University of Technology, Faculty of Electrical Engineering and Communication, Department of Electrical Power Engineering, Technická 10, 616 00 Brno, Czech Republic

Antonín Krása, Belgian Nuclear Research Centre, Belgium

Belgian Nuclear Research Centre, Institute for Advanced Nuclear Systems, SCK CEN, Boeretang 200, 2400
Mol, Belgium

Kamil Števanka, Brno University of Technology, Czech Republic

Brno University of Technology, Faculty of Electrical Engineering and Communication, Department of Electrical Power Engineering, Technická 10, 616 00 Brno, Czech Republic

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Published

2020-12-01

How to Cite

Šťastný, O. ., Katovský, K. ., Král, D. ., Krása, A. ., & Števanka, K. . (2020). ANALYSIS OF FAST NEUTRON TRANSPORT IN CHLORIDE SALTS USING MONTE CARLO METHOD. Acta Polytechnica CTU Proceedings, 28, 42–49. https://doi.org/10.14311/APP.2020.28.0042

Issue

Vol. 28 (2020): ŠIMÁNĚ 2020: Student Conference on Nuclear Engineering

Section

Articles